Thermal and fission neutron flux measurements in process tubing and in neutron activation test locations

Technical Report · Thu Feb 02 04:00:00 EST 1961

DOI:https://doi.org/10.2172/10124409· OSTI ID:10124409

Perkins, R W

Neutron activation analysis provides the extremely high sensitivity necessary for the measurement of many trace elements. Activation techniques are presently being used to measure the concentrations of various undesirable parent isotopes in reactor process tubing, slug jackets and their corrosion film, and in process vater and vater treatment chemicals. The interpretation of results from activation analysis are sometimes complicated by the fact that a given radioisotope may be produced by fission neutrons (threshold reactions) from other elements as well as by the more common thermal neutron (n,{gamma}) reactions. Shielding the sample with cadmium prior to irradiation or irradiating in the graphite reflector will minimize the contributions from thermal or fission neutrons, respectively. The purpose of this study has been to measure the ratios and magnitudes of the thermal and fission fluxes in process tubing and to compare these with values at locations where neutron activations can be performed. Also, it was of interest to measure the ratios and magnitudes of the thermal and fission fluxes from a point in the lattice to a point well into the graphite reflector, and to determine if the fission neutron spectrum as measured by two threshold reactions, changes appreciably over this region. These data will aid in selecting the most favorable available positions for activations with thermal neutron reactions or with threshold reactions.

• Research Organization: General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 10124409
• Report Number(s): HW--68377; ON: DE94006687
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100
220600
ACTIVATION ANALYSIS
FISSION NEUTRONS
HANFORD PRODUCTION REACTORS
MEASURING METHODS
NEUTRON FLUX
NEUTRON SPECTRA
PIPES
REACTOR KINETICS
REACTOR LATTICES
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
THEORY AND CALCULATION
THERMAL NEUTRONS